A digital fuel physics monitoring method and system suitable for heavy water reactors

Abstract

The application discloses a kind of digital fuel physics supervision method and system suitable for heavy water reactor, it is related to nuclear reactor fuel management technical field, system includes data acquisition module, document scale calculation interface, system management module and central processing module, central processing module configuration basic data, new fuel, FCO, spent fuel, dry storage area management unit.Method is standardized by data acquisition, whole-process digital control, dynamic monitoring and tracing three steps, realize fuel full life cycle closed-loop management.System adopts PDA to cooperate bar code / RFID to realize entity information acquisition and offline synchronization, constructs hierarchical correlation model, with new fuel isolation control, FCO closed-loop approval, spent fuel transfer verification, fine authority control and other functions, can improve management efficiency, reduce human error, strengthen data tracing and operation standardization, guarantee nuclear safety, provide support for management decision, suitable for heavy water reactor fuel physics supervision and whole-process management.

Description

Technical Field

[0001] This invention relates to the field of nuclear reactor fuel management technology, and in particular to a digital fuel physics monitoring method and system suitable for heavy water reactors. Background Technology

[0002] As an important type of nuclear reactor, heavy water reactors occupy an important position in the nuclear energy field due to their characteristics such as non-stop refueling and strong fuel adaptability. In particular, in models such as the CANDU (Canadian deuterium-uranium heavy water reactor), the replacement of fuel rod bundles can be completed under full power operation of the reactor, which places extremely high demands on the real-time and precision of fuel management.

[0003] Traditional heavy water reactor fuel physical monitoring relies primarily on manual records and paper ledgers. From parameter verification upon receiving new fuel and channel positioning during core refueling to status tracking during spent fuel transfer, all data must be manually entered by operators. This approach is not only inefficient—for example, recording and verifying a single refueling operation often requires 2-3 staff members working together for several hours—but also carries a significant risk of human error. Issues such as data transcription errors and location marking deviations occur frequently. There have even been instances where mismatches between refueling instructions and actual rod bundle types have led to potential localized power fluctuations in the core.

[0004] Meanwhile, fuel management involves multiple independent stages. Data from scenarios such as new fuel storage rooms, core refueling machines, spent fuel storage pools, and dry storage facilities are scattered across different recording systems, lacking a unified digital link. When it is necessary to trace the entire lifecycle status of a batch of fuel, manual retrieval and cross-comparison from multiple ledgers are required, often taking several days to complete, which is difficult to meet the nuclear safety regulatory requirements of "instant traceability and full controllability".

[0005] Furthermore, as heavy water reactors age, the types of fuel become increasingly diverse, and refueling strategies become more complex. Traditional systems are unable to provide real-time analysis and early warning of fuel status. For example, if spent fuel is stored in the storage pool for longer than a safety threshold, or if damaged fuel is transferred without meeting time limits, traditional management methods cannot detect and intervene in a timely manner, posing potential risks to reactor operational safety.

[0006] Existing digitalization efforts are mostly limited to single stages, failing to establish a closed-loop management system covering the entire process. Inconsistent data formats and incompatible interfaces between systems result in significant "information silos," hindering the provision of holistic decision support for refueling engineers. Therefore, developing a comprehensive digital fuel physics monitoring method and system suitable for heavy water reactors is crucial to solving these problems. Summary of the Invention

[0007] The purpose of this invention is to provide a digital fuel physical monitoring method and system suitable for heavy water reactors, replacing the traditional manual paper management mode, solving the problems of low fuel management efficiency, large errors, difficulty in traceability, non-standard processes, high safety risks and information silos, realizing digital control, accurate traceability and safety supervision of the entire fuel life cycle, and improving the fuel management efficiency and nuclear safety level of heavy water reactors.

[0008] To achieve the above objectives, the present invention provides a digital fuel physics monitoring system suitable for heavy water reactors, comprising: The data acquisition module interacts with portable scanning devices to collect physical identification, technical parameters, and location information of pallets, trays, bar bundles, and waste baskets, and supports offline data synchronization. The central processing module is equipped with a processor, a storage unit, and multiple functional units, including: The basic data management unit is used to store and maintain basic information about entities, and supports information query, retrieval, and automatic matching and synchronization with portable scanning devices; New Fuel Management Unit: Used to perform new fuel receiving, transfer and outbound transportation, rejection, isolation and isolation release operations, and manage the entry, storage and query of corresponding documents; FCO Management Unit: Used to generate refueling instructions (FCO), guide the core loading and unloading work according to the refueling process, and manage the entry, storage and query of corresponding documents; The spent fuel management unit is used to handle the transfer, secondary transfer, unconventional transfer, dismantling, shipment and loading operations of spent fuel, and manage the entry, storage and query of corresponding documents; The dry storage area management unit is used to perform spent fuel basket loading, transfer, non-routine transfer and shipment operations, and manage the entry, storage and query of corresponding documents; The system also includes: The document balance interface is used to export nuclear material balance data and provides query and statistics of material change history data; The system management module is used to maintain user information, configure role permissions, and set system parameters.

[0009] Preferably, the portable scanning device in the data acquisition module is a PDA device, the entity identifier includes a barcode or RFID tag, the technical parameters include fuel type, manufacturer and production batch, and the offline data synchronization supports data integrity verification and conflict handling mechanisms.

[0010] Preferably, the basic data management unit is configured with a hierarchical association model of "plate box - bar bundle - pallet - waste basket". The basic information stored in the basic data management unit includes unique entity codes, initial status parameters and historical operation records. The status parameters include pending receipt, received, loading, unloading completed, isolated and shipped.

[0011] Preferably, the new fuel management unit is equipped with an isolation control subunit, which is used to control all isolated fuel that is rejected in the new fuel loading area or fails the inspection when receiving new fuel, record the reason for isolation, isolation time, person in charge and conditions for release, and automatically trigger the inventory status update and notification mechanism when the isolation status changes.

[0012] Preferably, the FCO (Fuel Change Order) management unit specifically includes: The instruction generation subunit automatically generates a refueling instruction table (FCO) based on the core status parameters, including the refueling channel, number and type of rod bundles, and refueling sequence. The process management sub-unit executes the preparation, review, approval, execution, and closed-loop management of FCO according to the material change process, and records the operators and time of each step; The document management sub-unit is associated with the generation, signing, and archiving of loading and unloading orders, and supports tracing all documents throughout the process by FCO number.

[0013] Preferably, the spent fuel management unit sets verification rules for the transfer operation. The verification rules stipulate that only fully loaded pallets are allowed to be transferred from the receiving pool to the main storage pool, and unloaded pallets are forcibly restricted to storage in the damage area.

[0014] Preferably, the role permissions configured in the system management module include administrator, FCO compiler, auditor, operator, and queryer, wherein: the administrator has full-function operation permissions; the FCO compiler can only operate the instruction compilation function of the FCO management unit; the auditor is responsible for the approval of FCO and key documents; the operator performs on-site operations for fuel transfer and loading / unloading; and the queryer only has data query and report viewing permissions, and all role permissions can be dynamically adjusted and permission change logs are recorded.

[0015] A digital fuel physics monitoring method suitable for heavy water reactors, applied to the aforementioned system, includes the following steps: S1. Data Acquisition and Standardization: Entity information is acquired through the data acquisition module, and a standardized database is established through the basic data management unit to support data synchronization with portable scanning devices; S2. Full-process digital management and control: Dynamic management of all stages of the fuel lifecycle is implemented through a central processing module, specifically including: New Fuel Management: Execute receiving plan preparation, Gama inspection record, complete new fuel receiving, transfer and transportation, rejection, segregation and segregation release operations through the new fuel management unit, generate corresponding documents and archive them; Core refueling management: Refueling instructions are generated through the FCO management unit, and after approval, loading and unloading operations are guided. The core status before and after refueling is recorded, and corresponding documents are generated and archived. Spent fuel management: Track the transfer path of spent fuel, process transfer, secondary transfer, non-routine transfer, decomposition, shipment and loading operations through the spent fuel management unit, generate corresponding documents and archive them; Dry storage area management: The dry storage area management unit performs basket loading, transfer and shipping operations, records the location of the waste basket and heat parameters, generates corresponding documents and archives them; S3. Dynamic monitoring and traceability: Real-time display of fuel distribution status in various regions through an interactive graphical interface, display of recorded operation data and corresponding documents based on role permissions, and support for tracing back the entire lifecycle information by entity number.

[0016] Preferably, in the core refueling management process, after the refueling command is executed, the differential pressure measurement time and power reduction status need to be recorded, which are confirmed by the operator's electronic signature, and the system automatically updates the fuel composition data of the core channel.

[0017] In the spent fuel management process, the non-routine transfer step must record the reason for the transfer, the approver, and the safety measures. After the transfer, the rod bundle list of the source pallet and the target pallet should be updated simultaneously, and a non-routine transfer report should be generated.

[0018] According to specific embodiments provided by the present invention, the present invention discloses the following technical effects: 1. Improve management efficiency and reduce human error. The system achieves automatic collection and synchronization of entity information through the data acquisition module, replacing the traditional manual recording mode and reducing the workload of repetitive data entry; the central processing module achieves full-process digital control to standardize operations, avoid human judgment bias, reduce operational errors in key aspects of fuel management, and significantly improve the efficiency of refueling.

[0019] 2. Strengthen data traceability and consistency The basic data management unit achieves traceability of fuel lifecycle data through unique entity coding and a hierarchical association model of "plate box - rod bundle - pallet - waste basket". It supports tracing back the status changes, operation records and related documents of any entity by any entity number; the offline data synchronization mechanism ensures that the system data is consistent with the on-site status in real time, meeting the nuclear safety supervision requirements of "full controllability and traceability".

[0020] 3. Standardize operating procedures and improve safety. Each management unit implements rigid constraints on the operation process through preset rules. For example, the reason for isolating fuel must be recorded and confirmed by two people before it can be released; the transfer of spent fuel is only allowed to pass through fully loaded pallets; and FCO instructions must be compiled, reviewed, and approved in a closed-loop management process. This technical approach prevents violations and reduces the safety risks of reactor core operation.

[0021] 4. Fine-grained access control to ensure system security The system management module achieves clear operational control through detailed role-based permissions, preventing unauthorized operations; the dynamic adjustment of permissions and change logging function further enhance the security and compliance of system operation and maintenance.

[0022] 5. Supports decision analysis and facilitates refined management. The document balance interface can export standardized balance data and refueling history statistics. The graphical interface displays the fuel distribution status in real time, providing intuitive data analysis support for refueling engineers. This facilitates the optimization of refueling strategies, reasonable inventory planning, and adapts to the refined management needs of refueling without stopping the reactor in heavy water reactors. Attached Figure Description

[0023] To more clearly illustrate the technical solutions in the embodiments of the present invention or the prior art, the drawings used in the embodiments will be briefly introduced below. Obviously, the drawings described below are only some embodiments of the present invention. For those skilled in the art, other drawings can be obtained based on these drawings without creative effort.

[0024] Figure 1 This is a schematic diagram of system form relationships for an embodiment of digital fuel physics monitoring applicable to heavy water reactors according to the present invention.

[0025] Figure 2 This is a business process diagram of an embodiment of the present invention.

[0026] Figure 3 This is a flowchart of the FCO process according to an embodiment of the present invention.

[0027] Figure 4 This is a diagram illustrating the numbering rules for spent fuel storage baskets according to an embodiment of the present invention. Detailed Implementation

[0028] The technical solutions of the embodiments of the present invention will be clearly and completely described below with reference to the accompanying drawings. Obviously, the described embodiments are only some embodiments of the present invention, and not all embodiments. Based on the embodiments of the present invention, all other embodiments obtained by those skilled in the art without creative effort are within the scope of protection of the present invention.

[0029] To make the above-mentioned objects, features and advantages of the present invention more apparent and understandable, the present invention will be further described in detail below with reference to the accompanying drawings and specific embodiments.

[0030] Example This paper describes the specific implementation of the present invention in detail using a real-world application scenario of a CANDU reactor (which employs a non-stop power refueling method) in a certain location. This embodiment only lists several possible scenarios that may occur during the management process; the actual implementation of the technical solution relies on the business processes of the heavy water reactor.

[0031] (I) System Deployment and Initialization 1. Hardware Configuration Data acquisition module: Equipped with 10 industrial-grade portable data acquisition devices (PDAs) that support offline scanning, are waterproof and dustproof, and have a built-in barcode / RFID tag dual-mode scanning module for collecting physical identification of pallets, bar bundles, trays and waste baskets; Central processing module: Deployed on a dedicated server in the power plant, with specifications of a quad-core processor, 64GB of memory, 1TB of storage, and equipped with an Oracle database to store entity data and operation logs; A graphical user interface with interactive features: 20 client computers are set up in the main control room (MCR), refueling control room, fuel workshop and other locations to access system functions through a web interface; Document weighing interface: Interacts with the power plant's existing PDA synchronization dock (supporting USB data transfer) and weighing system (providing an XML format data interface). The process of physical operations in the heavy water reactor is as follows: Figure 2 As shown, the document categories generated during the management process are as follows: Figure 1 As shown.

[0032] 2. Basic data initialization Import initial data using the basic data management unit: Plate and container information: Enter data for several new fuel plates and containers, including unique code, manufacturer (Plant 202, designated nuclear fuel supplier), batch, and fuel type. Simultaneously enter the ledger information for returned plates and containers (new fuel plates and containers that fail gamma testing and need to be returned to Plant 202). Rod bundle information: Associate the panel box with the internal rod bundles, record the rod bundle number, uranium-235 abundance, and clearly define the functional areas, their numbers, and purposes, specifically including: S-118: New fuel storage room, used for the warehousing, temporary storage and isolation management of new fuel pallets; R-110: New fuel loading area, used for pre-loading preparation of new fuel rod bundles and pre-loading verification of the core; The drill passage is a dedicated passage for core refueling drills and equipment function verification. Only drill rod bundles are allowed to pass through, and it is forbidden to affect normal core operation. R-001: Spent fuel unloading pool, used for temporary reception and initial sorting of spent fuel unloaded from the reactor core; S-124: Spent fuel receiving pool, used for receiving spent fuel (including normal spent fuel bundles and drill bundles) after it is transferred from the unloading pool to the drill channel, and for sorting damaged fuel bundles; S-126: The main spent fuel storage pool, used for the long-term storage of intact spent fuel rod bundles (including qualified training rod bundles); S-124F: Permanent storage area for damaged spent fuel rod bundles, used for permanent isolation and storage. S-172: Spent fuel loading area, used for centralized management and control of spent fuel before loading and shipping; Container information: Enter and number several pallets and several spent fuel baskets, as well as the specifications of the pallets and spent fuel baskets, and distinguish between normal spent fuel pallets (standard pallets loaded with intact spent fuel rod bundles) and damaged fuel pallets; Location coding: Define the coordinate rules for the new fuel storage area (S-118), new fuel loading area (R-110), spent fuel unloading pool (R-001), spent fuel receiving pool (S-124), spent fuel main storage pool (S-126), damaged permanent storage area (S-124F), and spent fuel loading area (S-172), which are completely matched with the location of each area.

[0033] (II) Implementation of the new fuel management process 1. The new fuel and training rod bundle are received via the new fuel management unit. After the new feed trays and training rod bundles supplied by Plant 202 arrived, the fuel administrator used a PDA to scan the barcodes on the trays and the unique markings on the training rod bundles, respectively. New fuel pallets: The system automatically matches the receiving plan, enters the gamma inspection results, selects the storage location in the S-118 new fuel storage room, and generates a receiving document after submission. At the same time, a new fuel loading order (the official document for loading new fuel into the reactor core) is also generated. Unqualified pallets are marked as return pallets and can be returned to Plant 202. Exercise rod bundle: The system automatically matches the exercise plan, enters the verification results, assigns a unique permission identifier for the exercise channel, generates an exercise rod bundle receiving document, and only allows transfer to the exercise channel, prohibiting entry into the normal new fuel flow link; The basic data management unit automatically updates the status of the corresponding entities and synchronizes it to the graphical interface.

[0034] 2. Isolation Operation For pallets that fail inspection, isolation is implemented through the new fuel management unit: the isolation reason, the person in charge, and the isolation time are entered through the isolation control subunit; the system automatically marks the pallet as isolated in the inventory map of the S-118 new fuel storage room and restricts its transfer operation; When the quarantine is lifted, the reason for lifting must be entered and confirmed by the operator's electronic signature. The status will be updated to "received" and the vehicle can then be transferred to the R-110 new fuel loading area to await loading.

[0035] 3. Preparation for loading new fuel After the isolation is lifted, the qualified new fuel pallets are transferred from the S-118 new fuel storage room to the R-110 new fuel loading area. After unpacking, normal new fuel bundles are extracted to complete the pre-loading verification and prepare for core loading.

[0036] (iii) Implementation of FCO management processes, such as Figure 3 As shown.

[0037] 1. FCO preparation and approval The material change engineer logs into the system and selects the corresponding operating area through the FCO management unit: Normal refueling: Using qualified new rod bundles in the R-110 new fuel loading area as the refueling source, and the reactor core as the target area, the system automatically reads the core status parameters. Refueling drill: Using the drill rod bundles supplied by Plant 202 as the refueling source, the drill channel is selected as the target area, and the system automatically locks the exclusive permissions for the drill to prevent interference with normal core operation. The instruction generation subunit generates a refueling instruction based on the core / drill channel status parameters, including the refueling channel, bar bundle type, quantity, refueling sequence, and loading position; The process management sub-unit executes the approval process according to the process: the compiler submits (status "pending review") → issues the material change instruction form → (MCR) the reviewer confirms (status "pending approval") → the shift leader approves (status "effective"). The system records the operation time and signature of each step.

[0038] The document management sub-unit pre-associates new fuel loading orders and spent fuel unloading orders / drill unloading orders to prepare for subsequent execution and traceability.

[0039] 2. Loading and unloading procedures The system automatically associates the corresponding documents: Normal refueling: Link to new fuel loading order and spent fuel unloading order; Material changeover drill: This includes drills of the rod bundle receiving form and the unloading form. The loading operator scans the bar bundle code using a PDA: Normal refueling: After the rod bundle verification is completed in the R-110 new fuel loading area, the normal new rod bundle is pushed into the reactor core, the pushing sequence is recorded, and the system updates the core graphical interface in real time. Refueling Drill: The loading and unloading of the drill rod bundles are completed in the drill channel without affecting the normal operation of the reactor core. After the drill rod bundles are unloaded, they are transferred to the S-124 spent fuel receiving pool. The unloading operator unloads the normal spent fuel rod bundles from the reactor core and transfers them to the R-001 spent fuel unloading pool for temporary reception. After initial sorting, the normal spent fuel rod bundles are transferred to the S-124 spent fuel receiving pool. After unloading is completed, the operator enters the differential pressure measurement time and power reduction status into the system. After electronic signature confirmation, the process management subunit updates the FCO status to "closed loop" and the core channel data is automatically archived.

[0040] (iv) Implementation of the spent fuel management process 1. Receiving and sorting of spent fuel (including training rod bundles) Normal spent fuel rod bundles are transferred from the R-001 spent fuel unloading pool to the S-124 spent fuel receiving pool, while the exercise fuel rod bundles unloaded from the exercise channel are also transferred to the S-124 spent fuel receiving pool. Rod bundle sorting is completed in the S-124 spent fuel receiving pool: Intact fuel bundles (including qualified training fuel bundles) are transferred to intact fuel pallets and then transported to the S-126 spent fuel main storage pool for long-term storage. Damaged fuel bundles (including damaged fuel bundles used in drills) are transferred to damaged fuel trays, and some are transferred to the damaged fuel carousel for processing. After processing, intact fuel bundles are returned to S-124, and damaged fuel bundles are transferred to the S-124F permanent damaged fuel storage area for permanent isolation. Damaged and defective pallets are directly transferred to the S-124F permanent storage area for damaged materials.

[0041] 2. Normal transfer operation When spent fuel is transferred from the S-124 spent fuel receiving pool to the S-126 spent fuel main storage pool, the system executes the verification rules through the spent fuel management unit: only fully loaded pallets are allowed to be transferred, and incomplete pallets are forcibly restricted to storage in the S-124F damaged permanent storage area; after a normal spent fuel pallet shows as fully loaded, transfer is allowed. The operator enters the transfer path, generates a transfer record, and updates the pallet position coordinates synchronously.

[0042] 3. Damaged fuel and unconventional transfer handling For rod bundles marked "damaged" (including damaged drill rod bundles), the system automatically prompts storage conditions, restricting them to only the S-124F permanent damaged storage area; after disassembly, the storage container and location of each rod are entered, the system associates the "rod bundle-container" relationship, generates a disassembly record, and the damaged single rod container can be shipped to area 401.

[0043] Non-routine transfer: Before the transfer is executed, the reason for the transfer, the approver and the security measures are recorded. After the transfer, the bar bundle list of the source pallet and the target pallet is updated synchronously, and the system automatically generates a non-routine transfer report for archiving.

[0044] (v) Implementation of Dry Storage Area Management Process 1. Loading spent fuel into baskets Through the dry storage area management unit, the operator selects the normal spent fuel pallet from the S-126 spent fuel main storage pool and transfers it to the S-172 spent fuel loading area to perform the basket loading operation: the system automatically assigns the basket slots and records the slot number and cumulative heat of each rod bundle; the basket numbering rules are as follows... Figure 4 As shown.

[0045] Once the basket is loaded, a document is generated, and the basket status is updated to "loaded".

[0046] 2. Lack of basket distribution and unconventional ball movement Routine transfer: After the spent fuel basket completes the shipment verification in the S-172 spent fuel loading area, it is transferred to the dry storage area, and the system records the transfer time; Non-routine transfer: When executing a transfer, record the reason, approver and security measures, update the location status of the storage basket synchronously, and generate a non-routine transfer document for archiving; When shipping, a shipping order is generated, and the spent fuel is shipped from the dry storage area to the spent fuel processing plant, with the status updated to "shipped".

[0047] (vi) Document Balance and System Management 1. Exporting Balanced Data At a scheduled time each month, the previous month's nuclear material balance data is exported through the document balance interface unit, including: new fuel received at Plant 202, core refueling consumption, spent fuel inventory and shipments in various regions such as S-118 / S-126 / S-172; It supports querying historical records by time, operation content, and other conditions, and generates statistical reports in PDF format.

[0048] 2. Example of access control Configure role permissions in the system management module: Administrator (e.g., "System Engineer"): Can modify all module parameters; FCO programmers (such as "material change engineers") can only operate the "instruction creation" function of the FCO management unit; Auditors (e.g., "shift supervisors") have approval authority over FCOs and key documents; Operators (e.g., "field technicians"): can only perform on-site operations such as transfer, loading and unloading; When permissions are changed (e.g., "Zhang Gong" is upgraded from operator to auditor), the system automatically records the change log (including the operator, time, and content of the change).

[0049] The remaining technical features in the above embodiments can be flexibly selected by those skilled in the art to meet different specific practical needs according to actual circumstances. Modifications and variations made by those skilled in the art that do not depart from the spirit and scope of the present invention should be within the protection scope of the appended claims. In the above description, numerous specific details have been set forth to provide a thorough understanding of the present invention. However, it will be apparent to those skilled in the art that these specific details are not necessary to implement the present invention. In other instances, to avoid obscuring the present invention, well-known techniques, such as specific construction details, operating conditions, and other technical conditions, have not been specifically described.

[0050] This document uses specific examples to illustrate the principles and implementation methods of the present invention. The descriptions of the above embodiments are only for the purpose of helping to understand the method and core ideas of the present invention. Furthermore, those skilled in the art will recognize that, based on the ideas of the present invention, there will be changes in the specific implementation methods and application scope. Therefore, the content of this specification should not be construed as a limitation of the present invention.

Claims

1. A digital fuel physics monitoring system suitable for heavy water reactors, characterized in that, include: The data acquisition module interacts with portable scanning devices to collect physical identification, technical parameters, and location information of pallets, trays, bar bundles, and waste baskets, and supports offline data synchronization. The document balance interface is used to export nuclear material balance data and provides query and statistics of material change history data; The system management module is used to maintain user information, configure role permissions, and set system parameters. The central processing module is equipped with a processor, a storage unit, and multiple functional units, including: The basic data management unit is used to store and maintain basic information about entities, and supports information query, retrieval, and automatic matching and synchronization with portable scanning devices; New Fuel Management Unit: Used to perform new fuel receiving, transfer and outbound transportation, rejection, isolation and isolation release operations, and manage the entry, storage and query of corresponding documents; FCO Management Unit: Used to generate refueling instructions (FCO), guide the core loading and unloading work according to the refueling process, and manage the entry, storage and query of corresponding documents; The spent fuel management unit is used to handle the transfer, secondary transfer, unconventional transfer, dismantling, shipment and loading operations of spent fuel, and manage the entry, storage and query of corresponding documents; The dry storage area management unit is used to perform spent fuel basket loading, transfer, non-routine transfer and shipment operations, and manage the entry, storage and query of corresponding documents.

2. The digital fuel physics monitoring system for heavy water reactors according to claim 1, characterized in that: The portable scanning device in the data acquisition module is a PDA device, the entity identifier includes a barcode or RFID tag, the technical parameters include fuel type, manufacturer and production batch, and the offline data synchronization supports data integrity verification and conflict handling mechanisms.

3. The digital fuel physics monitoring system for heavy water reactors according to claim 1, characterized in that: The basic data management unit is set up with a hierarchical association model of "plate box - bar bundle - pallet - waste basket". The basic information stored in the basic data management unit includes the unique code of the entity, the initial state parameters and the historical operation records. The initial state parameters include waiting to be received, received, loading, unloading completed, isolated and shipped.

4. A digital fuel physics monitoring system suitable for heavy water reactors according to claim 1, characterized in that: The new fuel management unit is equipped with an isolation control subunit, which is used to record the reason for isolation, isolation time, person in charge and conditions for release. When the isolation status changes, the inventory status update and notification mechanism is automatically triggered.

5. A digital fuel physics monitoring system suitable for heavy water reactors according to claim 1, characterized in that: The FCO management unit specifically includes: The instruction generation subunit is used to automatically generate the refueling instruction table (FCO) based on the core status parameters, including the refueling channel, number and type of rod bundles, and refueling sequence. The process management subunit is used to prepare, review, approve, execute, and manage the FCO according to the material change process, and to record the operators and time of each step. The document management sub-unit is used for the generation, signing, and archiving of loading and unloading orders, and supports tracing all documents by FCO number.

6. A digital fuel physics monitoring system suitable for heavy water reactors according to claim 1, characterized in that: The spent fuel management unit sets verification rules for the transfer operation. The verification rules stipulate that only fully loaded pallets are allowed to be transferred from the receiving pool to the main storage pool, and unloaded pallets are forcibly restricted to storage in the damage area.

7. A digital fuel physics monitoring system suitable for heavy water reactors according to any one of claims 1 to 6, characterized in that: The system management module is configured with roles and permissions including administrator, FCO compiler, auditor, operator, and queryer. Among them: the administrator has full-function operation permissions; the FCO compiler can only operate the instruction compilation function of the FCO management unit; the auditor is responsible for the approval of FCO and key documents; the operator performs on-site operations for fuel transfer and loading / unloading; the queryer only has data query and report viewing permissions, and all role permissions can be dynamically adjusted and permission change logs are recorded.

8. A digital fuel physics monitoring method suitable for heavy water reactors, applied to a digital fuel physics monitoring system suitable for heavy water reactors as described in any one of claims 1 to 7, characterized in that, Includes the following steps: S1. Data Acquisition and Standardization: Entity information is acquired through the data acquisition module, and a standardized database is established through the basic data management unit to support data synchronization with portable scanning devices; S2. Full-process digital management and control: Dynamic management of all stages of the fuel lifecycle is implemented through a central processing module, specifically including: New Fuel Management: Execute receiving plan preparation and Gama inspection records; complete new fuel receiving, transfer and shipment, rejection, segregation and segregation release operations through the new fuel management unit, generate corresponding documents and archive them; Core refueling management: Refueling instructions are generated through the FCO management unit, and after approval, loading and unloading operations are guided. The core status before and after refueling is recorded, and corresponding documents are generated and archived. Spent fuel management: Track the transfer path of spent fuel, process transfer, secondary transfer, non-routine transfer, decomposition, shipment and loading operations through the spent fuel management unit, generate corresponding documents and archive them; Dry storage area management: The dry storage area management unit performs basket loading, transfer and shipping operations, records the location of the waste basket and heat parameters, generates corresponding documents and archives them; S3. Dynamic monitoring and traceability: Real-time display of fuel distribution status in various regions through an interactive graphical interface, display of recorded operation data and corresponding documents based on role permissions, and support for tracing back the entire lifecycle information by entity number.

9. A digital fuel physics monitoring method suitable for heavy water reactors according to claim 8, characterized in that: In the process of core refueling management, after the refueling command is executed, the differential pressure measurement time and power reduction status need to be recorded and confirmed by the operator's electronic signature. The system automatically updates the fuel composition data of the core channel.

10. A digital fuel physics monitoring method suitable for heavy water reactors according to claim 8, characterized in that: In the process of spent fuel management, the non-routine transfer step needs to record the reason for the transfer, the approver and safety measures. After the transfer, the rod bundle list of the source pallet and the target pallet should be updated simultaneously, and an non-routine transfer report should be generated.

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